WO2005061387A1 - Alimentation liquide au goutte-a-goutte et methode correspondante, obtention d'une solution de nitrate d'uranlye, et obtention d'une solution d'alcool polyvinylique - Google Patents

Alimentation liquide au goutte-a-goutte et methode correspondante, obtention d'une solution de nitrate d'uranlye, et obtention d'une solution d'alcool polyvinylique Download PDF

Info

Publication number
WO2005061387A1
WO2005061387A1 PCT/JP2004/019171 JP2004019171W WO2005061387A1 WO 2005061387 A1 WO2005061387 A1 WO 2005061387A1 JP 2004019171 W JP2004019171 W JP 2004019171W WO 2005061387 A1 WO2005061387 A1 WO 2005061387A1
Authority
WO
WIPO (PCT)
Prior art keywords
solution
preparing
polyvinyl alcohol
alcohol
nitrate
Prior art date
Application number
PCT/JP2004/019171
Other languages
English (en)
Japanese (ja)
Inventor
Masashi Takahashi
Original Assignee
Nuclear Fuel Industries, Ltd.
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Priority claimed from JP2003427059A external-priority patent/JP4334334B2/ja
Priority claimed from JP2004230327A external-priority patent/JP4621450B2/ja
Priority claimed from JP2004230385A external-priority patent/JP4639063B2/ja
Priority claimed from JP2004230481A external-priority patent/JP4679094B2/ja
Priority claimed from JP2004298114A external-priority patent/JP4596876B2/ja
Application filed by Nuclear Fuel Industries, Ltd. filed Critical Nuclear Fuel Industries, Ltd.
Priority to US10/583,906 priority Critical patent/US7628970B2/en
Priority to EP04807528.7A priority patent/EP1714943B1/fr
Publication of WO2005061387A1 publication Critical patent/WO2005061387A1/fr

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01G—COMPOUNDS CONTAINING METALS NOT COVERED BY SUBCLASSES C01D OR C01F
    • C01G43/00—Compounds of uranium
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • Stock solution for dropping method for preparing stock solution for dropping, method for preparing peranil nitrate solution, and method for preparing alcohol alcohol solution
  • the present invention relates to a stock solution for dropping, a method for preparing a stock solution for dropping, a method for preparing a peranyl nitrate solution, and a method for preparing a polyvinyl alcohol solution, and more particularly, to a true sphere used for manufacturing a fuel core for a high-temperature gas-cooled reactor.
  • Peranil nitrate-containing drop stock solution capable of producing ammonium biuranate particles of good degree
  • a method of preparing the drop stock solution and a method of preparing a peranil nitrate solution and a polyvinyl alcohol solution used for preparing the drop stock solution about.
  • a core structure into which fuel for a high-temperature gas furnace is charged is made of graphite having a large heat capacity and good high-temperature soundness.
  • This high-temperature gas furnace is evaluated as having high safety because no chemical reaction occurs even at high temperatures, and a gas such as helium gas is used as a cooling gas. Gas can be taken out safely. Therefore, the cooling gas heated to about 1000 ° C. enables heat utilization in a wide range of fields such as hydrogen production and the Iridaku Plant, as well as power generation.
  • a high-temperature gas-cooled reactor fuel to be charged into the high-temperature gas-cooled reactor generally includes a fuel core and a coating layer coated around the fuel core.
  • the fuel core is, for example, fine particles having a diameter of about 350 to 650 ⁇ m obtained by sintering silane dioxide into a ceramic.
  • the coating layer generally has a plurality of layer structures.
  • the coating layers having a four-layer structure are referred to as a first layer, a second layer, a third layer, and a fourth layer from the fuel core surface side.
  • the diameter of the coated particle composed of the fuel core and four layers is, for example, about 500 m to 1000 m.
  • Fuel nuclei are produced using an apparatus for producing ammonium biuranate particles as follows. First, the powder of Shiroi Uranium is dissolved in nitric acid to form a nitric acid perl solution. Next, the peranil nitrate solution is mixed with pure water, a thickener, and the like, and stirred to form a dripping stock solution. This dripping stock solution is stored in the dripping stock solution storage tank. The prepared dropping stock solution is at a predetermined temperature. After the viscosity is adjusted, it is transferred to the dropping nozzle device. The dripping nozzle device has one small diameter nozzle.
  • the transferred undiluted solution is dropped into the aqueous ammonia solution from a small-diameter nozzle, and the droplets falling into the aqueous ammonia solution react with peranil nitrate / ammonium biuranate from the surface of the aqueous solution to form an aqueous ammonia solution.
  • the droplets are present in the droplets for a sufficient time, formation of ammonium biuranate proceeds inside the droplets.
  • ADU particles ammonium biuranate particles
  • the ADU particles are washed and dried, and then roasted in the atmosphere to become uranium trioxide particles. Further, the uranium trioxide particles are reduced and sintered to become high-density ceramous uranium dioxide particles. The uranium dioxide particles are sieved, that is, classified to obtain fuel core fine particles having a predetermined particle diameter.
  • the high temperature gas reactor fuel is molded as a fuel compact or pebble sphere.
  • This fuel compact or pebble sphere is formed by pressing or molding a HTGR fuel into a solid cylindrical shape, hollow cylindrical shape or spherical shape together with graphite powder, a graphite matrix material which also has a binding agent, etc., and then fired. (See Non-Patent Documents 1 and 2)
  • Non-Patent Document 1 Reactor Materials, Ndbook, published on October 31, 1977, published by Nikkan Kogyo Shimbun
  • Non-Patent Document 2 Nuclear Power Handbook, published on December 20, 1995, Ohm Co., Ltd.
  • pure water and a thickener are added to a peranil nitrate stock solution, and the solution is stirred to obtain a dropping stock solution for forming ammonium biuranate particles.
  • the necessary detailed conditions are not described at all. With this alone, ammonium uranate particles with good sphericity and good internal structure Can not get, there is a problem.
  • peranil nitrate has been prepared by reacting nitric acid with uranium oxide, for example, uranium octanilide as follows.
  • nitric acid used is less than 2.66 moles per mole of uranium, from a stoichiometric point of view, unreacted uranium oxide, for example, triuranium octoxide, remains.
  • This unreacted uranium oxide, for example, unreacted triuranium octoxide is contained in the undiluted peranyl nitrate solution, so that it is not possible to produce ammonium biuranate particles as designed, and It was expected that it would not be possible to produce ammonium uranate particles with good sphericity.
  • An object of the present invention is to solve the conventional problems.
  • An object of the present invention is to provide a dripping stock solution from which a high-quality fuel core can be obtained.
  • An object of the present invention is to provide a method for preparing a dropping stock solution for producing ammonium biuranate particles that can be produced.
  • the present invention produces high-quality ammonium biuranate particles even though the nitric acid is reacted with the oxidized lanthanum under the reaction conditions in which the amount of the nitric acid to uranium is reduced.
  • peranyl nitrate solution which can reduce the burden on the environment. It is an object to provide a valuable preparation method.
  • a dropping stock for ⁇ beam particle production 4. a viscosity at 15 ° C OX 10- 2 - - heavy uranium acid ammonium 6.
  • dropwise stock which is a 5 X 10- 2 Pa 's Yes,
  • the undiluted solution according to claim 1 comprising peral nitrate, tetrahydrofurfuryl alcohol, and polybutyl alcohol.
  • a method for preparing a dropping stock solution for the production of ammonium biuranate particles comprising mixing a peranyl nitrate solution and tetrahydrofurfuryl alcohol to prepare a peranyl nitrate mixed solution, and dissolving polybutyl alcohol in water.
  • Preparing a polyvinyl alcohol aqueous solution mixing the polyvinyl alcohol aqueous solution and tetrahydrofurfuryl alcohol to prepare a polyvinyl alcohol solution, and mixing the peranil nitrate mixed solution and the polyvinyl alcohol solution. It is a method of preparing a dripping stock solution,
  • the volume is adjusted by mixing the peranil nitrate mixed solution and the polyvinyl alcohol solution while stirring, and then performing a degassing operation and an operation of adding pure water to the mixed solution.
  • a method for preparing a dripping stock solution characterized in that:
  • a method for preparing a peranyl nitrate solution used for preparing a stock solution for the production of ammonium biuranate particles comprising a molar ratio (AZB) force of nitric acid (A) and uranium (B).
  • AZB molar ratio
  • A nitric acid
  • B uranium
  • Claim 14 The method for preparing a peranil nitrate solution according to claim 12 or 13, further comprising a step of chemically treating NOx gas generated during a reaction between the nitric acid and uranium oxide.
  • a method for preparing a polyvinyl alcohol solution used for preparing a dropping stock solution for the production of ammonium biuranate particles comprising mixing polyvinyl alcohol and water,
  • a method for preparing a polyvinyl alcohol solution comprising: preparing a 9% by mass aqueous solution of polyvinyl alcohol; and mixing the aqueous solution of polyvinyl alcohol with tetrahydrofurfuryl alcohol.
  • aqueous ammonia dropwise stock When the droplet is dropped on the surface of the aqueous ammonia solution, the discharged droplet retains a spherical shape due to the surface tension and easily breaks or deforms due to the impact of the dropping undiluted solution on the surface of the aqueous ammonia solution. There is no clogging in the nozzle for dropping the stock solution.
  • a peranyl nitrate mixed solution is prepared by mixing a peranyl nitrate solution with tetrahydrofurfuryl alcohol (hereinafter sometimes referred to as THFA).
  • THFA tetrahydrofurfuryl alcohol
  • a polyvinyl alcohol aqueous solution (hereinafter sometimes referred to as PVA aqueous solution) prepared by dissolving polyvinyl alcohol (hereinafter sometimes referred to as PVA) in water is mixed with THFA to form a poly (vinyl alcohol).
  • a bull alcohol solution hereinafter sometimes referred to as a PVA solution
  • the above-mentioned nitric acid nitrate mixed solution and the PVA solution are mixed, the droplets discharged from the dropping nozzle cap are formed on the surface.
  • An undiluted solution having a viscosity that makes it difficult for the droplets to be broken or deformed due to the impact on the surface of the aqueous ammonia solution when a droplet of the undiluted solution is dropped onto an aqueous ammonia solution while maintaining a spherical shape by tension. Is prepared.
  • ammonium biuranate particles When ammonium biuranate particles are produced using the dropping stock solution prepared by the preparation method of the present invention, the ammonium biuranate particles have good sphericity, and thus have good sphericity. Fuel nuclei with good sphericity can be produced by using the proper ammonium biuranate particles.
  • the molar ratio of nitric acid to uranium (Z uranium nitrate) is set to 2.1 to 2.6, so that Udani uranium, for example, does not form a dissolution residue when dissolving octanoic acid uranium in nitric acid.
  • the amount can be reduced. Therefore, the final amount of waste liquid can be reduced, so that a peroxynitrate solution can be prepared at lower cost than the conventional method.
  • the stock solution having a predetermined uranium concentration can be dropped into the aqueous ammonia solution for each notch, thereby reducing internal defects.
  • Ammonia-uranium biuranate particles having a good particle size can be formed.
  • there is no dissolved residue in the prepared phenol nitrate solution. Can be manufactured. The use of ammonium uranate particles with good sphericity without internal defects produces fuel nuclei with good sphericity without internal defects.
  • the amount of nitrogen in the waste liquid can be reduced, and the amount of ammonium nitrate generated by the reaction between the aqueous ammonia solution and nitric acid can be reduced.
  • the amount of ammonium nitrate adhering to the surface of ammonium biuranate particles can be reduced. Therefore, it is possible to reduce the amount of hot water used for cleaning the ammonium nitrate adhered to the surface of the ammonium biuranate particles. Therefore, the load on the environment caused by the nitrogen in the waste liquid and the warm waste water can be reduced.
  • a PVA aqueous solution which is free from generation of a PVA dissolution residue and suitable for preparing a dropping stock solution containing peranil nitrate having a predetermined viscosity. Can be.
  • THFA and the PVA aqueous solution are mixed at a predetermined temperature with respect to the content of THFA contained in the undiluted solution containing peranil nitrate, the inside of the inside does not undergo deterioration due to gelling. It is possible to prepare a dropping stock solution having a predetermined viscosity capable of forming ammonium biuranate particles having good sphericity without defects.
  • FIG. 1 is a process chart showing a method for preparing a stock solution for dripping according to the present invention.
  • FIG. 2 is an explanatory view showing one example of a production apparatus for preparing a perchlor nitrate solution.
  • FIG. 3 is an optical micrograph showing a cross section of the ammonium biuranate particles obtained in Example 1.
  • FIG. 4 is a schematic diagram showing a method for evaluating the sphericity of a fuel core.
  • FIG. 5 is a graph showing the relationship between the yield of fuel nuclei and the viscosity of the stock solution for dripping.
  • FIG. 6 is an optical diagram showing a cut surface of ammonium biuranate particles produced in Comparative Example 2. It is a micrograph.
  • [0028] 1 is a reaction vessel
  • 2 is a nitric acid storage tank
  • 3 is an oxidizing uranium input hopper
  • 4 is a heating device
  • 5 is a NOx gas treatment device
  • 6 is a stirring device.
  • the stock solution for dropping according to the present invention is a solution containing peranil nitrate which is suitably used for producing a fuel core for a high-temperature gas-cooled reactor.
  • Dropping stock solution of the present invention 4. the viscosity thereof at 15 ° C 0 X 1 0- 2 - is a 6. 5 X 10- 2 Pa 's (40- value converted to 65cP).
  • the viscosity of the dropping solution is within the above range, it is possible to form ammonium biuranate particles having good sphericity.
  • the viscosity when the viscosity is lower than the lower limit, the shape of the heavy uranium ammonium particles may be deteriorated, and it may not be possible to form the heavy uranium ammonium particles having good sphericity. You. If the viscosity is larger than the upper limit, the viscosity of the undiluted solution is too high, which causes clogging of the drip nozzle and makes it impossible to drip, or the formation of ammonium uranate particles having internal defects. Sometimes.
  • the dropping stock having such viscosity, containing nitrate Uraniru and tetrahydrofurfuryl ⁇ alcohol and the poly Bulle alcohol, the viscosity of 4 at 15 ° C 0 X 10- 2 - 6. 5 X is 10- 2 Pa 's solution and the like.
  • water-soluble cyclic ethers having 14 to 14 carbon atoms such as oxetane, tetrahydrofuran, and dioxane, and 1 to 4 carbon atoms such as 2,5-tetrahydrofuranmethanol are used.
  • Water-soluble cyclic ethers containing an alkanol group that binds 13 alkanol groups to the cyclic ether can be mentioned.
  • polystyrene resin As an alternative to the above-mentioned polybutyl alcohol, synthetic polymers such as sodium polyacrylate and polyethylene oxide; carboxymethylcellulose; And starch-based polymers such as soluble starch and carboxymethyl starch, and water-soluble natural polymers such as dextrin and galactan.
  • the content of peranil nitrate in the dripping stock solution is usually 0.6-0.9moHJ / L.
  • the content of peranil nitrate is within the above range, a uranium diacid uranium fuel core having good sphericity can be produced with good reproducibility.
  • Uranium may form.
  • the content of the THFA in the whole stock solution for dropping is usually preferably from 40 to 50% by volume, more preferably from 43 to 47% by volume.
  • the content of the THFA in the dropping stock solution is within the above-mentioned range, it is possible to produce a diacid uranium fuel nucleus having good sphericity with good reproducibility. Poorly formed disulfide uranium fuel nuclei may be formed.
  • the content of the PVA in the stock solution for dropping is usually preferably 10 to 15 g / L.
  • the viscosity of the undiluted solution can be maintained at a high level, and a diacid uranium fuel nucleus having good sphericity can be produced with good reproducibility.
  • the content is less than 10 g / L, uranium dioxide fuel nuclei with low sphericity may be formed.
  • the content exceeds 15 g / L, a uranium dioxide nucleus having a defect in the internal structure may be generated.
  • the stock solution for dropping according to the present invention may contain other components as long as the object of the present invention is not hindered.
  • a thickener, a stabilizer and the like may be contained.
  • the dropping stock solution preparation method of the present invention comprises mixing a peranil nitrate solution with THF A to prepare a peranil nitrate mixed solution, dissolving PVA in water to prepare a PVA aqueous solution, and Basically, a PVA solution is prepared by mixing a PVA aqueous solution and THFA, and the PVA nitrate mixed solution and the PVA solution are mixed.
  • the peranyl nitrate solution can be obtained by the method for preparing a peranyl nitrate solution according to the present invention.
  • the molar ratio of nitric acid (A) to uranium (B) (AZB), that is, the number of moles of nitric acid is determined by For example, a value obtained by dividing by the number of moles of uranium in the octanoic acid uranium is important.
  • the peranil nitrate solution is obtained by reacting nitric acid with uranium oxide, for example, triuranium octoxide, according to the following reaction formula as described above.
  • the ratio is 2.1 -2.6 is preferred, especially 2.3-2.5.
  • uranium oxide for example, triuranium octoxide
  • the use amount of nitric acid increases, and the production cost of the nitric acid peral solution may increase.
  • the amount of nitrogen derived from nitric acid in the waste liquid increases, which may put a burden on the environment.
  • nitric acid having a concentration of 50% by mass or more, preferably 60% by mass or more is usually used.
  • the form of the uranium oxide for example, uranium oxalate, may be either granular or powdery, but it is a powdery form that is readily and completely dissolved in nitric acid. Preferably.
  • the nitric acid is reacted with the oxidized uranium, for example, octaniedated uranium at 70 to 110 ° C.
  • thiuranium acid may not be sufficiently dissolved, and a predetermined uranium concentration may not be obtained.
  • octanidanisan uranium it is preferable to use octanidanisan uranium as the anianidani uranium.
  • octahedral uranium for example, it is possible to use, for example, dylan uranium, uranium and the like.
  • the generated NOx gas is chemically treated. It is preferable to have a process.
  • Examples of the method of treating the NOx gas in the above step include a wet method in which the NOx gas is absorbed by an alkali and a dry method in which the NOx gas is reduced using a catalyst.
  • alkali examples include sodium hydroxide, sodium carbonate, magnesium hydroxide, calcium hydroxide, ammonia, and the like
  • examples of the catalyst include a three-way catalyst.
  • FIG. 2 shows an example of a production apparatus for preparing a peranil nitrate solution according to the present invention.
  • A is a nitric acid nitrate solution producing apparatus
  • 1 is a reaction vessel
  • 2 is a nitric acid storage tank
  • 3 is an oxidizing uranium charging hopper
  • 4 is a heating apparatus
  • 5 is a NOx gas processing apparatus
  • Reference numeral 6 denotes a stirring device.
  • the reaction vessel 1 is a vessel that reacts uranium acid, for example, triuranium octoxide with nitric acid to produce a peranyl nitrate solution.
  • the reaction vessel 1 is not particularly limited, but is preferably a vessel having corrosion resistance, heat resistance, pressure resistance, and airtightness.
  • Examples of the material of the reaction vessel 1 include an aluminum alloy, a magnesium alloy, a titanium alloy, and stainless steel.
  • the size and shape of the reaction vessel are not particularly limited. However, when criticality safety management is performed by shape limitation, the reaction vessel is formed into a size and shape having dimensions that satisfy the shape limitation. I do.
  • the nitric acid storage tank 2 is a tank for storing nitric acid, and is connected to the reaction container 1 via a pipe and a pump P2.
  • the material, size and shape of the nitric acid storage tank 2 are not particularly limited!
  • the nitric acid stored in the nitric acid storage tank 2 is sent into the reaction vessel 1 by the pump P2.
  • the liquid transfer may be continuous or intermittent.
  • the oxidizing uranium input hopper 3 stores oxidizing uranium, for example, octanodic uranium, and is connected to the reaction vessel 1 via a supply device (not shown). .
  • the material, size and shape of the uranium oxide hopper 3 are not particularly limited.
  • Uranium oxide, for example, triuranium octoxide, stored in the uranium oxide charging hopper 3 is charged into the reaction vessel 1 by the supply device.
  • a known supply device may be used.
  • a rotary feeder or a tape feeder may be used.
  • the heating device 4 is a device for heating the peranil nitrate solution.
  • a known heating device can be used, and examples thereof include a heating device having heating means using electricity, hot water, microwave irradiation, or the like. .
  • the NOx gas treatment device 5 is a device for detoxifying NOx gas, which is a by-product of the reaction, and is connected to the reaction vessel 1 via a pipe and a pump P1.
  • the size and shape of the NOx gas treatment device 5 are not particularly limited as long as the exhaust gas concentration after the treatment of the NOx gas concentration falls below the environmental standard value.
  • the stirring device 6 is not particularly limited, and examples thereof include a low-speed rotating stirrer and a medium-speed rotating stirrer.
  • the rotation speed of the stirring blade provided in the stirring device 6 is preferably 100 to 300 rpm, and the rotation thereof may be continuous or intermittent.
  • a peranyl nitrate solution can be produced as follows.
  • uranium oxide for example, octanoic acid uranium powder is charged from the uranium oxide charging hopper 3 into the reaction vessel 1.
  • nitric acid storage tank 2 a predetermined amount of nitric acid is sent from the nitric acid storage tank 2.
  • the temperature of the mixture in the reaction vessel 1 is kept constant, and the mixture is reacted for a predetermined time.
  • the peranil nitrate solution can be obtained by removing the solution after the reaction from the inside of the reaction vessel 1 using a known discharge means.
  • the peranyl nitrate solution prepared as above is mixed with THFA to form peranyl nitrate.
  • the THFA content in the whole stock solution is usually 40 to 50% by volume of the whole stock solution, and particularly preferably 43 to 47% by volume.
  • THFA in the whole of the dripping stock solution is within the above range, the content of peryl nitrate in the drops dropped from the dripping stock solution does not become too small, and a solution having an appropriate viscosity is formed.
  • the THF A used in the preparation of the peranil nitrate mixed solution is preferably from 50 to 99% by volume with respect to the whole stock solution from the viewpoint of mixing properties.
  • the mixing of the peranil nitrate solution with THFA is preferably performed while cooling to 15 ° C or less.
  • the mixing operation is preferably performed in a storage tank for preparing a stock solution for dropping, and the storage tank may be any device that can perform stirring of the peranyl nitrate solution and THFA at about 15 ° C or less. .
  • the PVA aqueous solution can be obtained by mixing PVA and water at normal temperature, preferably while heating.
  • dried PVA As the PVA!
  • the reason for using dried PVA is to accurately weigh PVA and to suitably produce ammonium biuranate particles capable of producing uranium dioxide particles with good sphericity with good yield. This is in order to prepare a dropping stock solution with good reproducibility.
  • the dried PVA can be obtained by sufficiently drying the absorbed PVA.
  • the degree of drying can be achieved by, for example, storing a desiccant that has absorbed moisture in a dryer containing a desiccant and maintaining a high vacuum under reduced pressure until no weight loss of PVA is observed. The degree can be mentioned.
  • the PVA can be obtained by storing the PVA in a desiccator or the like containing a desiccant and maintaining a high vacuum in the desiccator for at least one day.
  • the absorbed PVA is heated to a high temperature under normal pressure or reduced pressure.
  • a freeze drying method in which freezing and thawing are repeated under high vacuum may be employed.
  • the dried PVA is preferably stored under dry conditions to prevent moisture absorption, until used in the method of the present invention.
  • the treatment temperature such as the heating temperature and the treatment time such as the heating time in the heat drying or freeze drying are appropriately determined depending on the handling amount of PVA to be uniformly heat treated, the heating method, and the like. It is sufficient to judge that dry PVA was obtained in the state where the mass of PVA has been reduced. Heating conditions that cause deformation, alteration or decomposition of PVA should not be used. Appropriate heating temperature is 70-90 ° C and heating time is about 20 minutes to 2 hours.
  • the furnace or the tube contains the moisture-absorbed PVA, and the moisture-absorbed PVA is placed on a plate to be heated.
  • Heat treatment may be performed with hot air blown by laying a basket or storing the absorbed PVA in a basket.
  • the PVA is stored for a certain period in a container containing a desiccant such as activated carbon, activated alumina, or silica gel, for example, a desiccator.
  • a desiccant such as activated carbon, activated alumina, or silica gel, for example, a desiccator.
  • silica gel is preferable, and the storage period is appropriately determined depending on the type of PVA to be stored, the storage amount, and the like. It is only necessary to judge that dry PVA has been obtained in the state where the mass of PVA has been reduced.
  • the dried PVA obtained by heating the absorbed PVA is used, and the dried PVA is stored together with the desiccant.
  • PVA is preferably used.
  • the content of the PVA in the dripping stock solution is usually preferably 10 to 15 g / L.
  • the viscosity of the undiluted solution can be maintained at a good level, and the ammonium uranium biuranate particles having good sphericity can be produced with good reproducibility. If it is out of the above range, ammonium uranate particles having low sphericity may be generated.
  • the content ratio of the PVA in the aqueous PVA solution is usually 6 to 9% by mass, and particularly preferably 7 to 8% by mass.
  • nitric ⁇ La the viscosity of the dropping stock containing Le, 4. in 15 ° C OX 10- 2 - 6. 5 X 10- 2 Pa 's .
  • no PVA dissolution residue is formed in an aqueous PVA solution, for example, an aqueous polybutyl alcohol solution !.
  • the content ratio of the PVA in the aqueous PVA solution is less than 6% by mass, the viscosity of the finally obtained undiluted solution becomes too small to hinder dropping of the undiluted solution. Dissolution residue of PVA may be formed in aqueous solution.
  • the heating temperature for the melting that is, the temperature for heating the mixture of PVA and water, is preferably at least 75 ° C, that is, 75 ° C or more. When the heating temperature is 75 ° C. or more, there is no undissolved residue of PVA, and a uniform aqueous PVA solution can be prepared.
  • the mixture of PVA and water is usually stirred to improve the solubility.
  • the stirring time is usually preferably from 80 to 100 minutes. If the mixture is agitated and mixed while heating, water may evaporate and the water content in the mixture may decrease.However, the reduced amount of water may be caused by appropriately adding water to the heated mixture. To supplement.
  • the mixing ratio of the aqueous PVA solution and THFA is determined based on the amount of the THFA compounded with respect to the amount of the aqueous PVA solution at which the aqueous solution of PVA becomes 15-20% by volume of the total undiluted solution when the undiluted solution is prepared. It is adjusted so as to be 1 to 50% by volume, especially 30 to 40% by volume, based on the total amount of THFA in the stock solution.
  • THFA is added before the temperature of the mixture is lowered to 50 ° C, preferably 60 ° C at the lowest. Is preferred.
  • the undiluted solution is prepared by mixing the nitric acid / phenol mixed solution and the PVA solution.
  • the nitrate-perl mixed solution and the PVA solution are mixed with stirring, and then the volume is adjusted by performing a degassing operation and a pure water addition operation. With this operation, Uranium concentration can be kept constant. By doing so, it is possible to obtain ammonium biuranate particles having good sphericity and uniform uranium weight per particle without internal defects.
  • the uranium concentration of the stock solution after the volume and viscosity adjustment is preferably 0.6-0.9 md-U / L.
  • the uranium concentration of the undiluted solution after the volume adjustment is less than 0.6moHJ / L, the amount of PVA added becomes relatively large, the viscosity becomes too large, and the dropping nozzle is clogged. May not be formed, or there may be formation of ammonium biuranate particles having internal defects.
  • the undiluted solution prepared by the above-described method for preparing the undiluted solution is cooled to a predetermined temperature to adjust the viscosity, and then dropped into the aqueous ammonia solution using a small-diameter dropping nozzle.
  • the droplets dropped into the aqueous ammonia solution pass through the ammonia atmosphere before reaching the surface of the aqueous ammonia solution. Since the surface of the liquid droplet is gelled by passing through the ammonia atmosphere, deformation at the time of reaching the surface of the aqueous ammonia solution can be reduced.
  • Perchlor nitrate in the aqueous ammonia solution reacts sufficiently with ammonia to form ammonium biuranate particles (ADU particles).
  • ammonium biuranate particles are dried and then roasted in the air to form peranthium trioxide particles. Furthermore, the UO particles are reduced and sintered to become high-density ceramics UO particles. The uranium diacid particles are sieved, that is, classified to obtain a fuel core having a predetermined particle diameter.
  • the fuel for the high-temperature gas reactor is molded as a fuel compact or pebble sphere.
  • This fuel Compact or beveled spheres are formed by pressing or molding a HTGR fuel into a solid cylinder, hollow cylinder, or sphere together with a graphite matrix material consisting of graphite powder, binder, etc., and then firing. Is obtained.
  • a dropping stock solution was prepared under the following specific conditions. This condition is when the viscosity of the dropping stock solution is 15 ° C Odor Te 5. 2 X 10- 2 Pa 's ( a value obtained by converting the 52cP).
  • Uranium concentration ratio of undiluted solution after volume adjustment 0.76 mol / L
  • dripping stock solutions having various viscosities were prepared under different conditions. Then, a fuel core was manufactured as in the above embodiment. The viscosity of the undiluted solution was measured using a vibration type viscometer, Piscomate VM-1 A-L manufactured by Yama-Denki Co., Ltd.
  • the obtained ammonium biuranate particles were dried and then roasted in the air to obtain uranium trioxide particles.
  • the uranium trioxide particles were further reduced and sintered to obtain high-density ceramic uranium dioxide particles.
  • the uranium dioxide particles were sieved, that is, classified to obtain uranium oxide particles as fuel nuclei having a predetermined particle diameter. After that, the sphericity was evaluated using uranium oxide particles) for the obtained fuel core. Also, various viscosities After classifying the fuel cores in, the yield was evaluated.
  • the obtained ADU particles were polished, the cross section of the ADU particles was observed with an optical microscope, and the presence or absence of cracks and the like was evaluated to evaluate the internal structure. Observation of the cut surface confirmed that a uniform internal structure had been formed (see Fig. 3).
  • the sphericity of fuel nuclei was evaluated by the PSA method.
  • the PSA method uses a photodiode, a slit, and a light source as shown in FIG. Light emitted from the light source passes through the slit, and the shadow of the fuel nucleus (uranium particles) moving between the photodiode and the slit is measured by the photodiode.
  • the diameter of the fuel nuclei (dioxide uranium particles) measured by a photodiode is determined by the shading of the particles.
  • the sphericity of the fuel nucleus (dioxide uranium particles) is obtained by repeating the above measurement and performing the measurement in all directions of the fuel nuclei (dioxide uranium particles).
  • the diameter of one particle was measured 50 times, and the sphericity of 100 particles was determined from the ratio of the maximum diameter / minimum diameter. For example, if the sphericity is at least 95% of the total particle force of 1.2 or less, the sphericity is judged to be good.
  • outer diameter selection and sphericity selection are performed on the obtained fuel core particles.
  • the sieve operation was performed on the fuel core particles while changing the size of the sieve, and the fuel cores having a predetermined outer diameter range were accepted.
  • the sphericity selection is an operation that utilizes the fact that fuel nuclei particles are supplied to a surface that is inclined at a small angle and the nuclei with good sphericity fall vertically. As described above, the fuel core particles that dropped vertically were judged as acceptable.
  • a mixed solution obtained by adding 300 g of polyvinyl alcohol powder (PVA powder) to 4 L of pure water is stirred at 95 ° C for 90 minutes to obtain a PVA aqueous solution having a PVA concentration of 7% by mass. Got. No dissolved residue was found in the PVA aqueous solution thus obtained.
  • 4 L of tetrahydrofurfuryl alcohol (THFA) was added to the PVA solution at a temperature of 80 ° C. to obtain a PVA solution.
  • a peranil nitrate mixed solution obtained by mixing about 8 L of this PVA solution, about 9 L of peranil nitrate solution and about 7 L of THFA, and pure water were added to obtain a dropping stock solution containing peranil nitrate.
  • the viscosity of the dropping stock solution obtained in Example 2 was measured using a viscometer (manufactured by Yamaichi Electronics Co., Ltd.), at 12 ° C, 5. 5 X 10- 2 Pa 's Met. This, in terms of the viscosity of 15 ° C, 5. a 0 X 10- 2 Pa 's.
  • the dropping stock solution was dropped into aqueous ammonia to produce ammonium biuranate particles. After that, the dried diammonium uranate particles having been subjected to the drying step were cut into two at the diameter plane, and the cut surfaces were observed. As a result, it was confirmed that a uniform internal structure was formed.
  • the sphericity of the fuel core was evaluated by the sphericity evaluation method described above, and it was confirmed that the defect rate was 1% or less.
  • a dripping stock solution was obtained in the same manner as in Example 1 except that the amount of PVA added in the example was changed to 230 g. That is, an aqueous PVA solution having a PVA concentration of 5.4% by mass was used.
  • ammonium biuranate particles produced using this undiluted solution were dried and then roasted in the atmosphere to obtain uranium trioxide particles. Further, the uranium trioxide particles were reduced and sintered to obtain high density ceramic uranium particles. The uranium dioxide particles were sieved, that is, classified to obtain fuel nuclei (uranium dioxide particles) having a predetermined particle diameter.
  • Example 2 was repeated except that the amount of PVA was changed to 400 g.
  • the uranium powder was dissolved in nitric acid and stirred at 100 ° C. for 1.5 hours to prepare a Perr nitrate solution (2.4moHJ / L). 4 L of tetrahydrofurfuryl alcohol was mixed with this cellulose nitrate solution to obtain a cellulose nitrate mixed solution. On the other hand, tetrahydrofurfuryl alcohol is added to a 7% by mass aqueous solution of polyvinyl alcohol to form a polyvinyl alcohol solution. The mixture was stirred and mixed with the above-mentioned peranyl nitrate mixed solution, and water was added thereto to prepare a dropping stock solution. The viscosity of the stock solution was at 10 ° C 5. 3 X 10- 2 Pa 's (53cP). This is applicable to 4. 3 X 10- 2 Pa ' s at 15 ° C.
  • the thickener used at this time was previously subjected to an electric heating treatment at 85 ° C for 50 minutes, completely dried, and weighed.
  • 24 L of the stock solution prepared as described above was supplied to the stock liquid dropping device at a stock solution flow rate of 240 cm 3 Z via a stock solution flow control valve by a stock solution feed pump.
  • the raw liquid supplied to the raw liquid dropping apparatus is dropped from a raw liquid lower nozzle vibrated at a frequency of 75 Hz as a liquid drop in an ammonia gas atmosphere into a tank for storing a 28% aqueous ammonia solution. Ammonium biuranate particles were produced.
  • ammonium biuranate particles produced as described above were stored in a post-treatment tank, and aged at 80 ° C. for 1 hour while rotating the post-treatment tank. Thereafter, the substrate was washed with water at 80 ° C, further washed with ethyl alcohol at 70 ° C for 30 minutes, and then dried at 100 ° C for 3 hours to obtain dried ammonium biuranate particles. .
  • the dried ammonium biuranate particles obtained as described above were roasted at 550 ° C for 3 hours in the air to produce uranium trioxide particles.
  • the uranium trioxide particles were reduced at 600 ° C for 3 hours under a reducing atmosphere (hydrogen / nitrogen mixed gas atmosphere), and then sintered at 1550 ° C for 1 hour to form a ceramic material. To obtain uranium diacid particles.
  • the sphericity of the fuel core particles was determined by classifying (outer diameter selection and sphericity selection) the uranium dioxide particles obtained as described above, and the average was 1.04. Was. The yield of fuel core particles was 99.1% by mass.
  • Fuel core particles were produced in the same manner as in Example 1, except that polyvinyl alcohol powder stored in a desiccator loaded with silica gel for 3 days was used as a thickener. However, the viscosity of the stock solution was at 10 ° C 5. 1 X 10- 2 Pa 's (51cP). This corresponds to 4. 2 X 10- 2 Pa 's in viscosity at 15 ° C. As a result, the average sphericity of the fuel core particles was 1.05. The yield of fuel core particles was 98.5% by mass.
  • Fuel core particles were produced in the same manner as in Example 3, except that polyvinyl alcohol powder containing 9% by mass of water was used as a thickener. However, the viscosity of the stock solution, 4. a 4 X 10- 2 Pa 's ( 44cP) at 10 ° C. This corresponds to a viscosity of 3. 4 X 10- 2 Pa 's at 15 ° C. As a result, the average sphericity of the fuel core particles was 1.08. The yield of fuel core particles was 92% by mass.
  • Example 5 In a tank similar to that of Example 5, 5.1 kg of triuranium octoxide was charged, and 2.9 L of nitric acid was added little by little to this tank so that the molar ratio (Z uranium nitrate) became 2.05. After nitric acid was added, the heating device was operated, the liquid temperature in the tank was maintained at 100 ° C, and triuranium octoxide was reacted with nitric acid.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • Organic Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Inorganic Chemistry (AREA)
  • Geology (AREA)
  • Manufacturing & Machinery (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)

Abstract

Alimentation en liquide au goutte-à-goutte destinée à la fabrication de diuranate d'ammonium, caractérisée par une viscosité à 15 °C comprise entre 4,0 x 10-2 et 6,5 x 10-2 Pa.s; et procédé d'obtention d'une alimentation en liquide au goutte-à-goutte caractérisée en ce qu'elle consiste à mélanger une solution de nitrate d'uranyle et un alcool de tétrahydrofurfuryle en vue de l'obtention d'une solution de nitrate d'uranyle mélangée ; à dissoudre de l'alcool polyninylique dans de l'eau pour obtenir un solution aqueuse d'alcool polyvinylique ; à mélanger cette dernière solution et de l'alcool de tétrahydrofurfuryle pour obtenir une solution d'alcool polyvinylique ; puis à mélanger la solution de nitrate d'uranyle mélangée ci-dessus et la solution d'alcool polyvinylique ci-dessus. L'alimentation liquide susdécrite pour goutte-à-goutte permet d'obtenir un noyau de carburant de haute qualité.
PCT/JP2004/019171 2003-12-24 2004-12-22 Alimentation liquide au goutte-a-goutte et methode correspondante, obtention d'une solution de nitrate d'uranlye, et obtention d'une solution d'alcool polyvinylique WO2005061387A1 (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
US10/583,906 US7628970B2 (en) 2003-12-24 2004-12-22 Method of preparing feedstock liquid, method of preparing uranyl nitrate solution, and method of preparing polyvinyl alcohol solution
EP04807528.7A EP1714943B1 (fr) 2003-12-24 2004-12-22 Alimentation liquide au goutte-a-goutte et methode correspondante, obtention d'une solution de nitrate d'uranlye, et obtention d'une solution d'alcool polyvinylique

Applications Claiming Priority (10)

Application Number Priority Date Filing Date Title
JP2003427059A JP4334334B2 (ja) 2003-12-24 2003-12-24 硝酸ウラニル溶液の調製方法
JP2003-427059 2003-12-24
JP2004-230385 2004-08-06
JP2004230327A JP4621450B2 (ja) 2004-08-06 2004-08-06 滴下原液調製方法
JP2004-230481 2004-08-06
JP2004230385A JP4639063B2 (ja) 2004-08-06 2004-08-06 滴下原液
JP2004230481A JP4679094B2 (ja) 2004-08-06 2004-08-06 硝酸ウラニル含有滴下原液用ポリマー溶液調製方法
JP2004-230327 2004-08-06
JP2004298114A JP4596876B2 (ja) 2004-10-12 2004-10-12 重ウラン酸アンモニウム粒子製造用原液の調製方法
JP2004-298114 2004-10-12

Publications (1)

Publication Number Publication Date
WO2005061387A1 true WO2005061387A1 (fr) 2005-07-07

Family

ID=34714617

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/JP2004/019171 WO2005061387A1 (fr) 2003-12-24 2004-12-22 Alimentation liquide au goutte-a-goutte et methode correspondante, obtention d'une solution de nitrate d'uranlye, et obtention d'une solution d'alcool polyvinylique

Country Status (3)

Country Link
US (1) US7628970B2 (fr)
EP (1) EP1714943B1 (fr)
WO (1) WO2005061387A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108182981A (zh) * 2017-12-27 2018-06-19 中核北方核燃料元件有限公司 一种球形核燃料元件生产线增稠剂熬制装置及其使用方法

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4334316B2 (ja) * 2003-10-16 2009-09-30 原子燃料工業株式会社 重ウラン酸アンモニウム粒子製造装置
FR2936348B1 (fr) * 2008-09-23 2013-07-05 Commissariat Energie Atomique Procede de preparation d'un combustible mixte comprenant de l'uranium et au moins un actinide et/ou lanthanide mettant en oeuvre une resine echangeuse de cations.
DE102008055468B4 (de) * 2008-12-01 2010-09-02 Nukem Technologies Gmbh Verfahren und Anordnung zur Herstellung von Brennstoffkernen
EP2899725B1 (fr) * 2014-01-27 2018-04-25 Urenco Limited Contrôle de la température du matériau d'uranium dans une installation d'enrichissement d'uranium
JP7368620B2 (ja) 2019-11-04 2023-10-24 エックス－エナジー， エルエルシー 酸欠乏硝酸ウラニル溶液の調製

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH05279043A (ja) * 1992-03-27 1993-10-26 Nuclear Fuel Ind Ltd 重ウラン酸アンモニウム粒子の製造方法と製造装置
JPH06191851A (ja) * 1992-12-24 1994-07-12 Nuclear Fuel Ind Ltd 三酸化ウラン粒子の製造方法及びその製造装置
JPH06294881A (ja) * 1993-02-01 1994-10-21 General Electric Co <Ge> Ｕｏ２ スクラップの粉末とペレットを再生利用して高焼結密度のｕｏ２ ペレットを得る方法
JPH08151204A (ja) * 1994-11-24 1996-06-11 Japan Atom Energy Res Inst 亜化学量論的または化学量論的硝酸塩溶液調製方法
JPH0954187A (ja) * 1995-08-11 1997-02-25 Nuclear Fuel Ind Ltd ウラン酸化物粒子を原料とする核燃料ペレットの製造方法
JP2003509659A (ja) * 1999-09-06 2003-03-11 ユーロピーアン コンミュニティ （エセ） Ｍｏｘタイプの核燃料ペレットの製法

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4202793A (en) * 1973-10-26 1980-05-13 Agip Nucleare S.P.A. Production of microspheres of thorium oxide, uranium oxide and plutonium oxide and their mixtures containing carbon
DE2519747C3 (de) * 1975-05-02 1980-03-06 Kernforschungsanlage Juelich Gmbh, 5170 Juelich Verfahren zur Herstellung von Metalloxid- oder Metallcarbidteilchen
US4778665A (en) * 1986-09-09 1988-10-18 Mobil Oil Corporation Abatement of NOx in exhaust gases
JPH0666756A (ja) * 1992-08-24 1994-03-11 Tokyo Cosmos Electric Co Ltd 結露センサ感湿抵抗体用ペーストおよびその製造方法
US5698173A (en) * 1996-06-21 1997-12-16 The United States Of America As Represented By The United States Department Of Energy Purification of uranium alloys by differential solubility of oxides and production of purified fuel precursors

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH05279043A (ja) * 1992-03-27 1993-10-26 Nuclear Fuel Ind Ltd 重ウラン酸アンモニウム粒子の製造方法と製造装置
JPH06191851A (ja) * 1992-12-24 1994-07-12 Nuclear Fuel Ind Ltd 三酸化ウラン粒子の製造方法及びその製造装置
JPH06294881A (ja) * 1993-02-01 1994-10-21 General Electric Co <Ge> Ｕｏ２ スクラップの粉末とペレットを再生利用して高焼結密度のｕｏ２ ペレットを得る方法
JPH08151204A (ja) * 1994-11-24 1996-06-11 Japan Atom Energy Res Inst 亜化学量論的または化学量論的硝酸塩溶液調製方法
JPH0954187A (ja) * 1995-08-11 1997-02-25 Nuclear Fuel Ind Ltd ウラン酸化物粒子を原料とする核燃料ペレットの製造方法
JP2003509659A (ja) * 1999-09-06 2003-03-11 ユーロピーアン コンミュニティ （エセ） Ｍｏｘタイプの核燃料ペレットの製法

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108182981A (zh) * 2017-12-27 2018-06-19 中核北方核燃料元件有限公司 一种球形核燃料元件生产线增稠剂熬制装置及其使用方法
CN108182981B (zh) * 2017-12-27 2019-11-22 中核北方核燃料元件有限公司 一种球形核燃料元件生产线增稠剂熬制装置及其使用方法

Also Published As

Publication number Publication date
US7628970B2 (en) 2009-12-08
EP1714943A1 (fr) 2006-10-25
EP1714943A4 (fr) 2009-11-11
EP1714943B1 (fr) 2016-12-07
US20070178036A1 (en) 2007-08-02

Similar Documents

Publication Publication Date Title
JP6230540B2 (ja) リチウム二次電池用正極活物質及びそれを用いた正極
JP6196175B2 (ja) リチウム二次電池用正極活物質の製造方法及びそれに用いられる活物質前駆体粉末
JP5830178B2 (ja) リチウム二次電池用正極活物質の製造方法及びそれに用いられる活物質前駆体粉末
US4475948A (en) Lithium aluminate/zirconium material useful in the production of tritium
JP5830179B2 (ja) リチウム二次電池用正極活物質の製造方法及びそれに用いられる活物質前駆体粉末
ZA200606050B (en) Feedstock liquid, method of preparing feedstock liquid, method of preparing uranyl nitrate solution, and method of preparing polyvinal alcohol solution
CN1247521A (zh) 制备锂过渡金属取代物的方法
WO2005061387A1 (fr) Alimentation liquide au goutte-a-goutte et methode correspondante, obtention d&#39;une solution de nitrate d&#39;uranlye, et obtention d&#39;une solution d&#39;alcool polyvinylique
CN107134299B (zh) 一种钍基碳化物和/或钍基碳氧化物的陶瓷微球的制备方法
CN111952552B (zh) 一种玻璃态包覆型正极材料及其制备方法
JP4679094B2 (ja) 硝酸ウラニル含有滴下原液用ポリマー溶液調製方法
KR100812952B1 (ko) 지르코니아가 첨가된 중성자 흡수 소결체 및 이의 제조방법
JP4596876B2 (ja) 重ウラン酸アンモニウム粒子製造用原液の調製方法
JP3867971B2 (ja) 高温用トリチウム増殖材料
JP4621450B2 (ja) 滴下原液調製方法
KR102403373B1 (ko) 방사성 금속계 겔형 중간체의 제조 방법 및 방사성 금속계 겔형 중간체의 제조 장치
JP2007121128A (ja) ガドリニウム含有重ウラン酸アンモニウム粒子およびその製造方法、並びに高温ガス炉燃料用の燃料核、高温ガス炉用の被覆粒子および高温ガス炉用燃料。
JP4051732B2 (ja) 核燃料粒子の製造方法
JP4639063B2 (ja) 滴下原液
JP4636831B2 (ja) 重ウラン酸アンモニウム粒子の製造装置
JP2007084376A (ja) 重ウラン酸アンモニウム粒子の製造装置
JP2006038793A (ja) 燃料核粒子の製造方法
CN113698193A (zh) 一种耐腐蚀铝酸盐中子吸收材料及其制备方法
CN117800799A (zh) 一种AP-Al复合含能材料、制备方法及应用
JPH1172588A (ja) 核燃料粒子の製造方法

Legal Events

Date Code Title Description
AK Designated states

Kind code of ref document: A1

Designated state(s): AE AG AL AM AT AU AZ BA BB BG BR BW BY BZ CA CH CN CO CR CU CZ DE DK DM DZ EC EE EG ES FI GB GD GE GH GM HR HU ID IL IN IS KE KG KP KR KZ LC LK LR LS LT LU LV MA MD MG MK MN MW MX MZ NA NI NO NZ OM PG PH PL PT RO RU SC SD SE SG SK SL SY TJ TM TN TR TT TZ UA UG US UZ VC VN YU ZA ZM ZW

AL Designated countries for regional patents

Kind code of ref document: A1

Designated state(s): BW GH GM KE LS MW MZ NA SD SL SZ TZ UG ZM ZW AM AZ BY KG KZ MD RU TJ TM AT BE BG CH CY CZ DE DK EE ES FI FR GB GR HU IE IS IT LT LU MC NL PL PT RO SE SI SK TR BF BJ CF CG CI CM GA GN GQ GW ML MR NE SN TD TG

121 Ep: the epo has been informed by wipo that ep was designated in this application
DPEN Request for preliminary examination filed prior to expiration of 19th month from priority date (pct application filed from 20040101)
WWE Wipo information: entry into national phase

Ref document number: 10583906

Country of ref document: US

Ref document number: 2007178036

Country of ref document: US

NENP Non-entry into the national phase

Ref country code: DE

WWW Wipo information: withdrawn in national office

Ref document number: DE

REEP Request for entry into the european phase

Ref document number: 2004807528

Country of ref document: EP

WWE Wipo information: entry into national phase

Ref document number: 2004807528

Country of ref document: EP

WWE Wipo information: entry into national phase

Ref document number: 2006/06050

Country of ref document: ZA

Ref document number: 200606050

Country of ref document: ZA

WWE Wipo information: entry into national phase

Ref document number: 200480042034.1

Country of ref document: CN

WWP Wipo information: published in national office

Ref document number: 2004807528

Country of ref document: EP

WWP Wipo information: published in national office

Ref document number: 10583906

Country of ref document: US